ML20090B574
| ML20090B574 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/02/1987 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20090B375 | List: |
| References | |
| FOIA-91-106 1-PT-46.2A, NUDOCS 9203030467 | |
| Download: ML20090B574 (8) | |
Text
._. _.
RIQUEST TO CHANGE PROCEDURE arm-5.4 NORTH ANNA POVER STATION 71RGINIA P0kTR Page 1 of 1 07-09-87 I. ATPERVISOR RESPONSIBLE NR POLLOVING PROCDURE:
1 O ABNORMAL O CURVE B00E O OPERATING O kTLDING O ADMINISTRATIVE O EMERGENCY
$ PERIODIC TEST O
O ANNUNCIAICR O IN-SERVICE INSPECTION O HEALTE PHYSICS g
O CALIBRATION O MAINTENANCE O SPECIAL TEST O
O CnDfISTRY O NON-DESTRUCTIVE TEST O START-UP TEST O
PROCEDURE NO: / - g,.
2 UNIT No:
3 RTVISION DATE:
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CHANGES REQUESTG:
(GITI STEP NUMBER, EIACI SUGCESTED WORDING AND LIST RIPERENCES. STAPLE COPY OP PROCIDURE WITH SUGGESTED CHANGES MAREED TO THIS PORM.)
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RAASON POR CHANGES:
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7 GE REQUESTED ST:
8 DATE:
9 ACTION TAKIN:
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10 XES THIS CHANGE THE OPERATING METHODS AS DESCRIBED IN TEP. UFSARr' C YES 3 NO DOES THIS CHANGE INVOLVE A CHANGE TO THE TECH. SPECS /
O TES 3 NO DOES THIS CHANGE INVOLVE A POSSIBLE UNREVIEVED SATITY QUESTION /-
O TIS 3.NO IP ALL "NO", NO "$ATETT ANALYSIS" IS REQUIRED.
IP ANY "TES", A " SAFETY ANALYSIS" IS REQUIRID.
(10CTR50.59) APPROVED COPY TO BE PROVIDED TO LICENSING COORD. POR INCLUSTON IN ANhTAL REPORT.
RECO. WINDED ACTION:
1!
M PROVED O DISAPPROVED
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DOES THIS PROCEDURE CREATE A QA DOCUMENT /
TES S NO-C BT (COGNIZANT SUPERVISOB) 12 DATE:
13 REVIEkT.D ST QUALITT ASSURANCE:
CHANGES MADE TES O NO O -
14 BY:
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15 DATE 10 7g REVIEWED Y TATION NUCLEAR SAitu AND OPERATING COMMITTEE:
17 APPROVED O DISAPPROVED O APPROVED AS MODIPIED BY CC.WITTEE 1 4RMAN SIGNATURE:
18 DATE:
/p 19 NEW PROCEDURE REVISION DATE:
/
ACTION CCKPLETED BY:
21 DATE:
' 22 9203030467 910819
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WILLIAM 91-IO6 PDR
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PERIODIC TEST CRITIOUE NORTH ANNA POWER STATION VIRGINIA POVDL Periodic Test No 1
Io be Performed By:
2 Unit No J
1-PT-46.2A SRIFT TECHNICAL ADVISOR
_1,,
1 Test Titles 4
CONDENSER AIR EJECTOR RADIATION HONITOR ALARM SETPOINT CALCUIATION 3
i Tei.t frequency:
5
$PECIAL Unit Conditions Requiring Tests 6
MODE 1 s
Test Performed By:
7 Date Started: 8A Data Completed: 88 Test Results (To be completed by performer of test and Cognizant 9
Supervisor (s)):
1.
/ _ / Satisfactory
/
/ Unsatisfactc,7
/
/ Partial Procedure
- 2. The following problem (s) was encountered (use back of sheet for additional space):
- w. -
- 3. Corrective actii..t taken or initiated:
- 4. Work Order No.:
Dated:
Porvard to Cognizant Supervisor i
Test Reviewed and Approved By Cognizant Supervisor (s) or Designee:
10 Dates Reactor Engineer Dates Supervisor, Sury. 6 Test Consents:
Forward To Performance Engineer Comment (s) of Performance Engineer:
11 Stamps 12 l
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I 1-PT-46.2A Page 1 of 4 00-00-00 VIRGINIA POWER PERIODICTESTPROCED$.EPORNORTHANNAPOVERSTATIONUNITNO.:
1 TITLE: CONDENSER AIR EJECTOR RADIATION MONITOR ALARM SETPOINT CALCULATION
REFERENCES:
1.
1-PT-46. 2 2.
Calculational Basis for PT-46.2A, approved 10/1/87 (See Rev. 0) 3.
Letter to the NRC, 9/15/87 (serial no. 87-474A)
REVISION RECORD:
APPROVED CRAIRMAN STATION NUCLEAR SAFETY
,RIV.
NO.
PAGZ(S)
DATE AND OPERATING COMMITTEE l
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RECOMMENDED APPROVAL:~
l APPROVED BY:
1 CHAIRMAN STATION NUCLEAR SAFETY AND OPERATING COMMITTEI DATE:
SUPERINTENDFNT TECHNICAL SERVICES 1
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1-PT-46.2A Page 2 of 4 00-00-00 Initials 1.0 Purpose To determine the Condenser Air Ejector Radiation Monitor (1-RM-SV-121)
"HIGH" alarm setpoint, based on primary-to-secondary leakage, omamme 2.0 Initial conditions NOTE: If this is an initial startup, then previous pts may not be available.
2.1 The trend of the condenser air ejector radiation nordtor count rate from 1-PT-46.2 is available.
NOTE: If this is an initial startup, or a restart following a steam generator tube plugging outage, the initial leak rate is assumed to be 0 spd.
2.2 The S/G 1eak rate data from 1-PT-46.2 is available.
3.0 Precautions and Limitations 3.1 This trocedure must be performed prior.to entering Modo 1.
3.2 For an initial sta'rtup, or a plant startup following a S/G tube plugging outage, the previous S/C leak rate is assumed to be 0 spd.
3.3 For a plant startup, estimate the RCS gas activity, for 30% power, or any power level that the plant is arpect4d to operate at for an extended period, whichever is less.
3.4 To recalculate the air ejector radiation monitor (1-RM-SV-121,)
"HIGH" alarm setpoint, use the most recent measured RCS gas activity isotopics, if possible, or applicable. Otherwise estimate the RCS gas activity isotopics based on previous measured data and power history.
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1-PT-46.2A Page 3 of 4 00-00-00 3.5 To recalculate the air ejector radiation monitor (1-RM-SV-121)
"HIGH" alarm setpoint, use the most recent leak rate calculations based on 1-RM-SV-121. Several leak rate results may be averaged to better ascertain the primary-to-secondary leak rate.
4.0 Instructions 4.1 Record the most recent psimary-to-secondary leak rate data (based on 1-RM-SV-121) from 1-PT-46.2 on Attachment 6.1.
If this is a startup af ter a S/G tube inapection outage, record 0 spd total leakage on Attachment 6.1.
4.2 Estimate the RCS gas activity based upon previous measured data and the power history. Use 1-PT-46.2 (Atta'chmen't 6.10) for guidance. Record the estimated RCS gas activity on Attachment 6.1.
Recy$
4.3 rd the previous "HIGH" alarm setpoint for 1-RM-SV-121 on y
A;t'achment 6.1.
4.4 Record the current total Condenser Air Ejector Flow Rate on
..1.
4.5 Record the current count rate for 1-RM-SV-121 on Attachment 6.1.
4.6 Calculate the new *HIGH" alarm sstpoint for 1-RM-SV-121 using the equations at the Sottom of Attachment 6.1.
4.7 Immediately notify the Shif t Supervisor of the new alare setpoint.
4.8 Complete Attachment 6.2 and forward a copy to the Health Physics Shitt Supervisor.
l 4.9 Verify that the new setpoint has been implemented.
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1-PT-46.2A Page 4 of 4 00-00-00 4.10 Post an Operator Aid (ADM-19.27) next to 1-PJi-SV-121 stating the new setpoint in both cpe and gpd.
$.0 Acceptance Criteria 5.1 The new setpoint has been implemented and an Operator Aid has been posted.
6.0 A*.tachments 6.1 1-RM-SV-121 "HIGH" Alarm Setpoint Calculation 6.2 Memo to change the "High" alarm setpoint for 1-RM-SV-121.
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I 1-PT-46.2A.1 Page 1 of 1 00-00-00 1-EM-SV-121 *EIGH" Alarm Setpoint Calculation Recent Primary-toSecondary Leak Rate Data Based on 1-RM-SV-121 (from 1-PT-46.2):
Date(s):
Leak Rate (s):
Averages gpd RCS Gas Activity (uci/ gram)
Hessured:
Date:
Times Powers Xe-135:
Kr-87:
Ar-41:
Estimated Fort Date Times Powers Xe-13$:
KR-87:
Ar-41:
Total Condenser Air Ejector Flow Rate SCFH Current Count Rate for 1-RM-SV-121:
cpm Previous "RIGH" Alarm Setpoint s cpa This corresponds tot gpd e
New "HIGH" Alarm Setpoints eps This corresponds tot gpd eIf 1-RM-CV-121 is less than or equal to 80 cpm Setpoint (cpm) = 80 +
(20 rpo) (Ke-135 + Kr-87 + AR-41)
(2.92 x 10~4)(Air Ejector Flow Rate) e If 1-RM-SV-21 is greater than or equal to 80 cpa Setpoint (eps) = 80 + (leak rate + 10 rpd)(Xe-135 + Kr-87 + Ar-41 (2.92 x 10"#)(Air Ejector Flow Rate)
PREPARED BY:
DATE:
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1-PI-46.2A Attachnent 6.2 Page 1 of 1 00-00-00 MDO TO CHANGE THE *HICH" ALLEM SETPOINT TO 1-RM-SV-121 TO: Health Physics Shif t Supervisor North Anna Power Station PROM Shif t Technical Advisor Date Please immediately update the "HIGH" alarm setpoint to the Unit 1 Condenser Air Ejector Radiation Monitor (1-PJi-SV-121) as soon as possible, as follows:
Setpoint =
cpm This corresponds tot gpd 1
Date Shilt Technical Advisor
.-